IR 05000261/1987021
| ML14191A832 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 07/14/1987 |
| From: | Kahle J, Marston R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML14191A831 | List: |
| References | |
| 50-261-87-21, NUDOCS 8707230716 | |
| Download: ML14191A832 (10) | |
Text
A REGjj UNITED STATES o
NUCLEAR REGULATORY-COMMISSION REGION I1 101 MARIETTA STREET, ATLANTA, GEORGIA 30323
_j) V I 6 1987 Report No.:
50-261/87-21 Licensee: Carolina Power and Light Company 411 Fayetteville Street Raleigh, NC 27602 Docket No.: 50-261 License No.: DPR-23 Facility Name: H. B. Robinson Inspection Condued: June 22-26, 1987 Inspector:
R. R, arston Approved by: Kahle, Section Chief Si Di sion of Radiation Safety and Safeguards SUMMARY Scope: This routine unannounced inspection was conducted in the areas. of liquid and gaseous effluents, the radiological environmental monitoring program, and closeout of open item Results:
No violations or deviations were identifie PDR ADOCK 05000261 G
REPORT DETAILS 1. Persons Contacted Licensee Employees R. E. Morgan, General Manager
- R. M. Smith, Manager, Environmental and Radiation Control J. A. Eaddy, Supervisor, Environmental and Chemistry J. L. Harrison, Project Specialist, Environmental and Chemistry
- H. F. Watkins, Environmental and Chemistry Foreman
- B. A. Christensen, Environmental and Chemistry Foreman
- D. Gainey, Senior Specialist, QA/QC
- A. M. McCauley, Principal Engineer, ONS Other licensee employees contacted included two technicians and a Regulatory Compliance Aid NRC Resident Inspectors H. E. P. Krug, Senior Resident Inspector
- Attended exit interview 2. Exit Interview The inspection scope and findings were summarized on June.26, 1987, with those persons indicated in Paragraph 1 abov The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspector during this inspectio. Licensee Action on Previous Enforcement Matters This subject was not addressed in the inspection 4. Audits (80721, 84723, 84724)
Technical Specification 6.5.3.2.d requires audits of plant activities including the Offsite Dose Calculation Manual (ODCM)
and implementing procedures at least once per 24 months, the conformance of facility operation to all provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months, the Radiological Environmental Monitoring Program once per 12 months, and the performance of activities required by the Quality Assurance Program to meet the criteria of Regulatory Guide 4.15, December 1977, at least once per 12 month The inspectors reviewed the following audits conducted by licensee corporate personnel:
QAA/0020-86-04, Review, evaluate, and verify implementation of the Plant Operating Manual, Technical Specifications, and Corporate QA Program, May 12-16, 198 QAA/0020-87-04, Review, evaluate, and verify implementation of the Plant Operating Manual, Technical Specifications, and Corporate QA Program, May 11-15, 198 Areas covered in the above audits included:
(1) Environmental & Radiation Control (E & RC) Administration; (2) E & RC Calibration; (3) Environmental Monitoring; (4) Radiation & Respiratory Protection; (5)
ALARA Program; (6) Surveillance (Radiological);
(7) Process Control Program (Including Radwaste Shipping);
(8)
Reportable Occurrences (LERS);
(9) Verification of Corrective Action from Previous Audits; and (10) Plant Housekeeping Plant QA/QC personnel also conducted surveillances of the program The surveillances included:
o QASR 86-093, Verification of Implementation of the Radiological &
Environmental Technical Specifications (RETS), conducted June 23-27, 1986, covering effluent monitoring instrumentation, effluents, and environmental monitorin o QASR 86-096 conducted June 1986, covering environmental monitorin Audit QAA/0020-87-04 identified no items of concern and closed out three open items from previous audit No violations or deviations were identifie. Changes to the Program (80721, 84723, 84724)
Since the previous inspection in these areas, Chemistry and Environmental had split into two group Chemistry and Environmental was responsible for primary and secondary chemistry, auxiliary boilers, radiochemistry, PASS operation, emergency environmental monitoring team, environmental and
hazardous waste, and batch releas Control of Effluents and Technical Assistance was responsible for the counting room, releases, E & RC technical assistance, the emergency environmental monitoring team, reports, projects, and process monitor This group was also in the process of taking over calibration of the effluent monitors from Health Physic A licensee representative advised the inspector that liquid radwaste was now being processed by a Duratech (ion exchange) test system instead of evaporators for a one year test perio No violations or deviations were identifie. Implementation of the Radiological Environmental Monitoring Program (80721)
Technical Specification 3.17 requires the establishment of a radiological environmental monitoring program, the principal details of which are provided in Technical Specification Table 3.17-1. The inspector conducted a detailed review of the radiological environmental monitoring program to verify the implementation and to assess its compliance with the subject specificatio The inspection included the following:
(1) review and discussion of monitoring and surveillance procedures; (2) review of selected sampling collection data sheets (January 16 through June 26, 1987),
and Environmental Sampling Reports (January 1986 through May 1987); (3) review of Annual Environmental Radiological Monitoring Reports for 1985 and 1986, and selected monthly reports for 1987; and (4)
examination of two air particulate/radioiodine sampling stations, one surface water sampling station, and the five collocated NRC/licensee TLD station The inspection disclosed that the radiological environmental monitoring program was implemented in accordance with Environmental Technical Specification requirement The inspector obtained the quarterly licensee environmental TLD readouts for 1985 and 1986 for those TLDs collocated with NRC TLDs as specified in Inspection and Enforcement Manual Temporary Instruction (TI) 2500/22. The data was sent to Region I per the TI reporting requirement The inspector reviewed land-use census data for 1986 and 198 The program was conducted i.n accordance with Technical Specification 3.1 No violations or deviations were identifie. Implementation of the Meteorological Monitoring Program (80721)
A licensee representative stated that the meteorological system maintenance and calibration were conducted out of corporate headquarters, and that these records and the data records from the system were kept ther The inspector examined the meteorological system equipment, including indicators and recorders, and reviewed the logbook The logbooks covered the period from August 15, 1986, to the time of the
inspection, and provided dates of calibration as well as other service informatio No violations or deviations were identifie. Plant Radwaste Treatment Systems (84723, 84724)
a. Technical Specification 6.17.1 requires that licensee-initiated major changes to the radioactive waste systems be reported to the Commission in the Semiannual Radioactive Effluent Release Reports for the period in which the safety evaluation was reviewed by the Plant Nuclear Safety Committe The inspector reviewed the Semiannual Radioactive Effluent Release Reports for January-June 1986 and July-December 1986, and discussed radwaste systems with licensee personne Licensee representatives stated that no changes to the radwaste systems were implemented in 1986, and the change discussed in Paragraph 5 of this report will be reported in the Semiannual Radioactive Effluent Report for January-June 198 b. Technical Specifications 3.9.1, 3.9.2, 3.16.1, and 3.16.2 define the operating requirements and radioactive effluent limits of the liquid radwaste treatment system. Technical Specification 4.10.1 and Table 4.10-1 define the surveillance requirements. The inspector reviewed selected liquid effluent release permits for.the period of August 1986-March 1987 and discussed liquid radwaste operating experience with licensee personne Licensee personnel indicated that no major problems had been encountered since the last inspectio c. Technical Specifications 3.9.3, 3.9.4, 3.9.5, 3.16.3, 3.16.4, and 3.16.5 define the operating requirements and radioactive effluent limits of the gaseous radwaste treatment systems, including ventilation system Technical Specifications 4.10.2, 4.10.3, 4.10.4, and Table 4.10.2 define the surveillance requirements. The inspector reviewed selected gaseous effluent release permits forthe period of October 1986-March 1987. The inspector discussed operating experience with licensee personnel, who indicated normal system operabilit No violations or deviations were identifie.
Reactor Coolant Chemistry (84723)
Technical Specification 3.1.4 specifies the reactor coolant specific activity limits,.and Technical Specification 3.1.6 specifies the reactor coolant oxygen and chloride concentration limits. Technical Specification 4.1, -Table 4.1-2, defines surveillance requirements for the system. The inspector reviewed the Operating Chemistry Reports for January 1986 through June 12, 1987; the Shutdown Chemistry Reports for January 25-February 14, 1986, and March 28 through June 13, 1987; and the Monthly Chemistry Reports for January-May, 198 No violations or deviations were identifie. Air Cleaning Systems (84724)
Technical Specification 3.15 defines requirements for operability of the Control Room 'Filter System, and Technical Specification 3.16.3 defines the operating requirements for the gaseous radwaste and ventilation exhaust treatment system Technical Specification 4.12 specifies verification tests for the spent Fuel Building.filter system and the Containment Purge filter system, and Technical Specification 4.15 specifies verification tests for the Control Room filter syste The inspector reviewed completed test procedures for the following systems:
(1) HVE-1, Containment Purge System, conducted April 5-6, 1987; (2) HVE-2, Auxiliary Building Exhaust, conducted March 31, 1987; (3) HVE-3 & 4 Containment Recirculation, conducted May 22, 1987; and (4) HVE-19 Control Room Emergency Ventilation, conducted October 6, 1986 No violations or deviations were identifie.
Radioactive Liquid and Gaseous Effluent Monitoring Instrumentation (84723, 84724)
Technical Specifications 3.5.2, 3.5.3, and Technical Specification Tables 3.5-6 and 3.5-7 define the operating requirements for radioactive effluent monitoring and sampling of plant liquid and gaseous effluent stream Additionally, Technical Specifications 4.19.1, 4.19.2, and Technical Specification Tables 4.19-1 and 4.19-2 define the surveillance requirements for radioactive liquid and gaseous effluent monitoring and samplin The inspections reviewed selected logs and records for laboratory counting system The operating daily logs, calibration records, and QC records and charts for 1987 were reviewed for three GeLi systems, the two Tennelec LB 1000 (alpha and beta counting) systems, and the TC #460 C Packard 460 LS (liquid scintillator) syste No violations and deviations were identifie.
Inspector Followup Items (92701)
(Closed)
Inspector Followup Item 86-19-01:
Review changes to the Analytical Laboratory Program:
(1) Maintain performance trend charts for longer than a one month period; (2) Improve the review of QC trend data by supervisors and technicians; (3) Perform cross checks between detectors using as many geometries as possible; and (4) Use additional geometries in the interstation crosscheck progra The inspector reviewed the licensee's corrective action commitments and corrective action The corrective actions involved changes to various Chemistry, Environmental, and Radiochemistry procedure The control charts were still done for one month at a time, but were based on the annual calibration.. Required reviews were proceduralized, crosschecks within-and-between counting rooms were designated for more geometries, and a copy of the daily operations log was posted on each detecto.
Procedures (80721, 84723, 84724)
Technical Specification 6.5.1.1.1 requires that written procedures be established, implemented, and maintained covering in part:
a. The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33,.Rev. 2, February 1978; g. Radiological Environmental Monitoring Program implementing procedures; and Quality Assurance Program for effluent and environmental monitoring (using the guidance in Regulatory Guide 4.15, December 1977).
The inspector reviewed a selection of applicable procedures which had been changed since the last inspection (listed in Appendix I).
No violations or deviations were identifie. Semiannual Effluent Reports (84723, 84724)
Technical Specification 6.9.1.d requires the licensee to submit within 60 days of January 1 and July 1 of each year, routine Radioactive Effluent Release Reports covering the operation of the unit during the previous six months of operatio The reports shall include a summary of the quantities of radioactive materials released from the unit as outlined in Regulatory Guide 1.2 Additionally, the reports that are submitted 60 days after January 1 of each year shall include an assessment of radiation doses due to the radioactive liquid and gaseous effluents released from the station during the previous calendar yea The inspector reviewed the Semiannual Radiological Effluent Release Report for the period July 1-December 31, 198 The review included an examination of the liquid and gaseous effluent release data as well as dose estimate data. Selected data from this report and previous reports are presented in Table The inspector noted that the quantities of radionuclides released in both liquid and gaseous form were significantly lower than other Region II pressurized water reactors (PWRs).
The radiation doses from the primary effluent pathways were below the limits specified in 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operation No violations or deviations were identifie TABLE 1 Robinson -Nuclear Station Semiannual Effluent Release Summary 1984-1986 Year 1984 1985 1986 No. Abnormal Releases a. Liquid
0 0 Gaseous
0
Liquid Waste Released (gallons)
3.99E+6 3.54E+6 6.10E+6 Activity Released (Curies)
a. Liquid 1. Fission and Activation Products 4.07E-1 2.43E-1 2.01E-1 2. Tritium 1.34E+1 3.09E+2 3.42E+2 Gross Alpha
0
b. Gaseous 1. Noble Gas 1.04E+2 2.72E+3 6.59E+2 2. Halogens 4.59E-4 1.50E-2 1.07E-2 3. Tritium 2.22 8.85E+1 9.66 4. Gross Alpha
0
Dose Estimate (mrem)
a. Liquid Whole-body 3.27E-3 2.46E-2 6.64E-2 b. Gaseous 1. Whole-body 4.19E-2 3.73E-1 1.69E-1 2. Thyroid 7.10E-3 1.93E-1 3.45E-1
APPENDIX I Procedures Reviewed by Inspector Chemistry Procedures o
CP-001, Chemistry Monitoring Program, Revision 13, March 28, 198 o CP-002, Calibration Control, Revision 2, January 26, 198 o CP-003, Systems Sampling Procedure, Revision 6, March 12, 198 o CP-008, Control Charts, Revision 2, April 24, 198 Environmental Monitoring Procedures o
EMP-001, Environmental Sampling, Revision 9, January 7, 198 o EMP-002, Air Flowmeter Acceptance, Revision 2, May 22, 198 o EMP-010, Effluent and Waste Disposal Report, Revision 2, June 17, 198 *
EMP-013, Operation and Calibration of RMS-34, Revision 7, May 25, 198 o EMP-018, Gaseous High Level Sample Retrieval and Analysis, Revision 1, November 12, 198 o EMP-022, Gaseous Waste Release Permits, Revision 5, April 28, 198 o EMP-023, Liquid Waste Release and Sampling, Revision 4, May 14, 198 o EMP-024, RETS Surveillance, Revision 8, May 14, 198 o EMP-025, Gaseous Effluent Sampling and Analysis Requirements, Revision 8, May 12, 198 o EMP-028, Process Monitor Setpoint Determination, Revision 0, May 14, 198 Radiochemistry Procedures
RCP-106, Radiochemistry Laboratory Surveillance, Revision 3, January 19, 198 o RCP-115, Calibration and Operation. of the Tennelec LB 1000 Alpha/Beta Counter, Revision 0, February 2, 198 *
RCP-120, Tritium Sample Preparation and Analysis, Revision 4, January 30, 198 o RCP-121, Calibration of the Packard Model 460 Liquid Scintillation Spectrometer, Revision 4, January 12, 198 o RCP-130, Calibration of the Nuclear Data Gamma Spectroscopy System, Revision 6, January 12, 198 Engineering Surveillance Test Procedures o
EST-016, HVE-1 Containment Purge System, Revision 7, July 8, 1986 o
EST-017. HVE-2 Auxiliary Building Exhaust, Revision 4, July 8, 1986 o
EST-018, HVE-3 and 4 Containment Recirculation, Revision 4, July 8, 1986 o
EST-023, HVE-19 Control Room Emergency Ventilation, Revison 3, August 19, 1986